ML20011D246
| ML20011D246 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 12/15/1989 |
| From: | Boger B Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20011D247 | List: |
| References | |
| NUDOCS 8912260055 | |
| Download: ML20011D246 (5) | |
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UNITED STATES h~
NUCLEAR REGULATORY COMMISSION n
WASHINGTON, D. C,20S$5 t
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t POWER AllTHORITY OF THE STATE'0F NEW YORK DOCKET NO. 50-333 I
JAMES A. FITZPATRICK Nt' CLEAR POWER PLANT AMENDMENT TC FACILITY OPERATING LICENSE Amendment No. 147 License No. DPR-59 9:
Th'e Nuclear Regulatory Conmission (the Comission) has found that:
1.
A.
The application for amendment by Power Authority of the State of New York (the licenseei dated December 11, 1989, complies with the standards and requirements of the Atomic Energy Act' of 19Etc, as amended (the Act) and the Convission's rules and
. regulations set forth in 10 CFR Chapter I; 5.
_The-facility will operate in conforvity with the application, the provisions of the Act, and the rules and regulations of i
the Comission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Connission's reaulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amerhent is in accordance with 10 CFR Part 5; of the Connission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License l
No. DPR-59 is heceby amended to read as follows:
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l 8912260005 891215 PDR ADOCK 05000333 P
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(2) -Technical Specifications l
The. Technical Specifications contained in Appendices A and B, as revised through Anendment No.147, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance to be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION Bruce A. Boger, Assistant Director for Region I Reactors Division of Reactor Projccts - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
December 15, 1989 l
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ATTACHMENT TO LICENSE AMENDMENT NO. 147 FACILITY OPERATING LICENSE NO. DPR-59 DOCKET NO. 50-333
'i P.evise. Appendix A as follows:.
Pemove Pages Insert Pages 57 57 70b 70b 6
' 3.2 BASES (cont'd)
High radiation monitors in the main steam line tunnel have been provided to detect gross fuel failure as in the control rod.
The trip settings of approximately 300 percent of dougn flow I
drop accident. With the estabkshed setting of 3 times normal for this high flow or 40"F above maamum amtWent for high -
background, and main steam line isolation valve closure, temperatwo are such that uncovenng the core is prevented
. and fission product release is weihm hmits.
fissson product release is limited so that 10 CFR 100 guidehnes are not exceeded for this accedent. Reference Section 14.6.1.2 NE@hMwh h m i
FSAR. Dunng the Hydrogen Addition Test, the normal the e as M for h M N @ %d er background Main Steam Une Rareatrm t.evel is expected to E
Wh@hWMh l-increase by approximately a factor r45 at the M Wogen concentration as indicated in note 16 Table 3.1-1. With the criteria as the HPCI~
hydrogen addition, the fission product release would still be.
well withm the 10 CFR 100 guidelmes in the event of a control
- The reactor water cleanup system high Row temperature l
i rod drop accident.
instrumentation are aranged semilar to that for the HPCI. The trip settmgs are such that uncovenng the core is prevented and l
Pressure instrumentation is provided to close the main steam ssson pre rh h h h Isolation valves in the run mode when the main steam line pressure drops below 825 psig. The reactor pressure vessel The instrumentation which erwhates ECCS achon is arranged m thermal transeent due to an inadvertent openmg of the turbine a dud bus system. As for other vitalinstrumerwaarm arranged i
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bypass valves when not in the run mode is less severe than the
' in this fashion, the specslicahon preserves the effechweness of loss of feedwater analyzed in Section 14.5 of the FSAR, the system even during penods when mamtenance or testmg is -
therefore, closure of the main steam isolation valves for thermal '
bemg performed. An exception to this is when logic funchonal testmg is bemg performed.
transient protectacq when not in the run mode is not required.
l The HPCI high flow and temperature instrumentation are The control rod block funchons are provided to prevent excessrve control rod withdrawed so that MCPR does not de-provided to detect a break in the HPCI steam popog. Trippmg of this instrumentation results in actuation of HPCIisolation valves. Tripping logic for the high flow is a 1 out of 2 logic.
l Amendment No. 14,??,38,46,90, % > I47 57
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TABLE 32-2(Cont'd)
INSTRUMENTATION THAT INITIATES OR CONTROLS
~i THE CORE AND CONTAINMENT CCAM.ING SYSTEMS 4
't Mirwnum No.
of Operable instrument Total Number of '
Item Channels Per instrument Channels Pronded by Design No.
Trip System (1)
Trip Function Trip LevelSettog for Both Trip Systems Romerks 29 1
ACIC Steam Line/
<4rF Above 2 inst. Channels Canna lensseme Valve Area Temperature max. ambient in RCIC Subsystem 30 1
RCIC Steam Line 100> P>50 psig 2 Inst. Channels CloseisolationValves low Pressure in RCICSubsystem j
31 1
HPCI Turbme Steam
<160in H O dp 2 Inst. Channels Closeisolation Valves I-2 Line High Flow in HPCISubsystem 32 1
RCIC Turbme High
< 10 psig 2 Inst. Channels CloseIsolaban Valves Exhaust Daphragm
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33 1
HPCI Turbine High
< 10 psig 2 inst. Channels Close isotahon Valves Exhaust Daphragm Pressure in HPCISubsystem i
34 1
LPCI Cross-Connect NA 1 Inst. Cinnnels initiates annunciation i
Position l
when valveis not closed 35 1
HPCI Steam Une 100> P>50 psig 2 Inst. Channels Close Isolation Valve l
Low Pressure in HPCI Subsystems 36 1
HPCI Steam Une/
< 40*F 2 Inst. Channels Close isolation Valve Area Temperature above max. ambient in HPCI Subsystem Amendment No. 4,46,68, % *107 70b l
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